licensing analysis of rpv and bop blowdown for the event of … · 2017-05-22 · lp turbine#6 tdv...

1核子工程組Engineering Simulator

Licensing Analysis of RPV and BOPBlowdown for the Event of FWLB with RELAP5-3D/K for Lungmen

ABWR Containment Design

Prepared by：Thomas K.S. LiangAffiliated to : Institute of Nuclear Energy Research,

Taiwan


Contents

IntroductionSystem Modeling with RELAP5-3DAssumptionsResultsConclusionsSpecial Issue of LPFL Injection Bypass


Introduction

Conventionally, the limiting break for BWR containment design is the recirculation line break.In the ABWR design, the jet pumps driven by the recirculation loops are replaced by the reactor internal pumps(RIPs).As a result, the limiting break for ABWR containment design shifts to theFeedwater Line Break (FWLB).


Introduction


Introduction

(1) Critical flow at the break ends or the internals, such as FW sparger and venturi;

(2) Flashing of RPV inventory and FW near the break; (3) Run out and coast down of the FW pumps;(4) Steam extractions to FW heaters and FWP turbines; (5) Flashing of saturated water initially stored inside

the FW heater shell sides and MSR drain tanks;(6) Energy release from saturated water and system metal,(7) Cold water transportation from the main condenser to

the break; and (8) ECC injections and associated level variations.

Essential Processes to be calculated


CDSR

FWHTR#3

NPP4 System Simulation Diagram

Steam

Water

Extraction to MSR RHTR #2

Extraction to MSR RHTR #1

GV

NRV

NRV

CV

GV

GV

GV

CV CV

CV

ISOV

LFCV

ISOV

Extraction to HTR#1

Vent from MSR RHTR #2 Drain Tank

Vent from MSR RHTR #1 Drain Tank

Vent from HTR#1

Drain from HTR#6

Drain from MSR RHTR #2 Drain Tank

Drain from MSR RHTR #1 Drain Tank

ORF

ORF

MSLHeader

Extraction to LP FW HTR

Drain from MSRSeparator Drain Tank

ISOV

HP Turbine MSR

RHTR #1Drain Tank

RHTR #2Drain Tank

SeparatorDrain Tank

LP Turbine

ORF

CP

TDFWP

TDFWP

MDFWP

RPV

FromSea

ToSea

MFPT

FWHTR#4

FWHTR#5

FWHTR#6

FWHTR#2

FWHTR#1

NRV

ORF Vent from HTR#2

CV CV

NRV

CV CV CV

Extraction to HTR#2

GV

GV

System Modeling with RELAP5-3D-Modeling Scope-


System Modeling with RELAP5-3D

HPCF

051~059040

061~069060

Act

ive

Cor

e C

hann

el

Byp

ass

Cha

nnel

RCIC

FW

3 RIPsw/o MG Set

3 RIPsw/ MG Set

070

041~049

071071-1

072

036

036-3036-2036-2

036-1034

032

033030 030

028 028

026 026

024 024

022022

020020

010 012014

004

002

FlowRestrictor

100

120

140

160

MSL_A

MSL_B

MSL_C

121

101

141

161

MS Nozzle

102

122

142

162

MS LineSection 1

SRV003A110

SRV004A111

SRV003B130

SRV004B131

SRV003C150

SRV004C151

SRV003D170

SRV004D171

103

123

143

163

MS LineSection 2

SRV005A112

SRV005D172

SRV006D173

SRV006A113

SRV007B134

SRV005B132

SRV006B133

SRV007C154

SRV005C152

SRV006C153

3 RIPsw/ MG Set

1 RIPsw/o MG Set

011

MSL_D

-123 hydraulic nodes-137 junctions-123 heat slabs

Modeling of RPV and Steam Lines



Modeling of Main Steam & Turbine Systems

401MSL

Header

405

403

407

409

411

GV

SP423

From HPTextraciton

To Heater #3

From MSLHeader

CV CV CV

To MSR RHTR#2

extraction

461

MFPT413

extraction

ORF ORF

NRV

To Heater #1

MSR

1st heaterdrain tank1st heaterdrain tank

2nd heaterdrain tank2nd heaterdrain tank

Separatordrain tankSeparatordrain tank

To MSRRHTR#1To MSRRHTR#1

473

NRV

HPTLPT

To CDSR

465

469FromRPV

463

477

481

471

475

479

483

417

415

419

421 4

33

439

443

449

453

455

451

435

441

445

To Heater #1

To Heater #3

To Heater #4

To Heater #5

To Heater #6

467

To Heater #1

To Heater #2

431

437

447

425

427

GV

To CDSR

RHTR#2 RHTR#1501501

502502

503503

504504

505505

506506

507507

508508

511511 512512

513513 516516

519519

514514 517517 520520

522522

532532

533533

534534

535535

515515 518518 521521

536536

540540

541541

542542

543543

544544

545545

546546

547547

550550

551551

552552

553553

554554

555555

556556

557557

561561560560 562562

563563 564564565565

566566 567567

570570

571571574574577577

580580

572572

573573

575575

576576

578578

579579 581581

509509 510510

492

491

493

494

MSIV586586

587587

588588

589589

590590

591591

592592

593593

496

495

497

498

594594

595595

596596

597597

-141 hydraulic nodes

-126 junctions



Modeling of Condensate & Feedwater Systems

TDJ

TDJ

Exhaustfrom MFPT

From Sea

To Sea

TDJ

Drain fromHTR#6

TDJ

Extraction fromLP Turbine#2

Drain from MSRSPRTR Drain Tank

To RPV

Exhaust fromLP Turbine

Vent from HTR#1

ORF

TDJ

ISOV

ISOV

LFCV

ISOVTDV

TDV

TDV

CDSR

601

CP603

HTR#4

TDV

TDFWP647

665

651

673675

TDFWP648

MDFWP649

HTR#5

HTR#2HTR#1

HTR#3

Extraction fromHP Turbine #5

Drain from MSRRHTR #1 Drain Tank

Drain from MSRRHTR #2 Drain Tank

Vent from MSRRHTR #2 Drain Tank

Vent from MSRRHTR #1 Drain Tank

HTR#6

663

Extraction from HPTurbine exhaust

653

ORF

655

Drain toHTR#2

TDJ

TDV

TDJTDJTDJ

Drain fromHTR#2

637

639

Vent from HTR#2

TDJ


TDVDrain fromHTR#3

TDJ


TDVDrain fromHTR#4

TDJ


TDVDrain fromHTR#5

627

629

617

619

607

609

Vent from HTR#3Vent from HTR#4

Vent from HTR#5

Vent from HTR#6

661

625 615 605

CV

Drain toHTR#3TDV

CV

Drain toHTR#4TDV

CV

Drain toHTR#5TDV

CV

Drain toHTR#6TDV

CV

TDV Drain toCDSR

CV

611

657

621

613

623

633

643

641

631

659

667

669

644

645

646

635

TDJ

TDV

Drain fromHTR#1

701

702703

706

707 708

709

710

715716

717

718

719

725726

727

728

729

735

737

738

739

736

745

746

747

748

749

750

753

754

751

752

755

756

761

762

764

765

770

771

773

774

781

782

711

712

713

720

721

722

730

731

732

740

741

742

763

766

767

768

772

775

776

777

671

677

783

786 785 784679

-158 nodes

-151 junctions

-133 slabs



Modeling of FW pump-shaft-turbine module

T D F W P

M F P T4 6 5 4 6 6G V

T o C D S R5 6 25 6 2

56 456 4 5 655 654 6 7

5 6 15 6 1F ro m M S R 9 09 0 19 09 0 1

6 4 49 6 9 019 6 9 01

6 4 79 69 0 29 69 0 2

6 3 57 457 45 F ro m H T R # 3

6 5 17 5 27 5 2

7 6 17 6 17 3 67 3 6

IS O VT o H T R # 2

2 0 5 9 0 92 0 5 9 0 9S H A F T

1000 2000 3000 4000 5000 6000 7000

Capacity [m3/hr]

600

700

800

900

1000

Hea

d [m

]

Turbine Driven Feedwater PumpRELAP5-3DOriginal



Modeling of Inboard & Outboard Breaks

(Outboard Check Valve)(To RPV) (Venturi)

Feedwater Line Header

Feedwater Line A

Feedwater Line B

Inboard BreakNode

(Inboard Check Valve)

Outboard Break Node

Primary Containment Wall


Assumptions

Initial ConditionsParameter Initial Value

(INER)Initial Value(GE)

Reactor Thermal Power [MWt]

4005.0(102 %)

4005.0(102%)

RPV Dome Pressure [MPa]

7.31(102 %)

7.31(102%)

RPV Core Flow [kg/s]

16,107(111.1 %)

16,110(111.1%)

RPV Narrow Range Water Level [cm]

426.0 427.0

Steam and Feedwater Flow [kg/s]

2177.8(102 %)

2174.0(102%)

Feedwater Temperature [°C]

216.9(102 %)

216.9(102%)


Sensitivity Studies

RPV modeling: (1) initial core flow

70 80 90 100 110 120Core Flow [%]

360

370

380

390

400

RPV

Initi

al W

ater

Inve

ntor

y [m

3 ]

RELAP5-3DGE Data (102% of Rated Power)

0 100 200 300 400 500 600 700Time [sec]

-100000

0

100000

200000

300000

400000

500000

Brea

k Fl

ow M

ass

Inte

grat

ion

[kg]

Core Flow85%102%111%

Effect of Core Flow on the Initial RPV Inventory Effect of Initial Core Flow on the Accumulated RPV Blowdown Mass


Assumptions

Plant OperationsExtraction steam continues to enter the feedwater heater and the feedwater

pump turbines until steam inventory is depleted or blocked by the non-return valves designed to protect main turbines;

Non-safety systems and components are assumed to fail in ways that maximum the amount of water mass and energy blowdown;

Feedwater flow to the vessel through the unbroken line continuesintermittently through the event, depending on the feedwater line and RPV pressures.

MSIVs will be fully closed within 3.0-4.5 seconds[3-4], and 3.0 seconds is conservatively assumed for inboard break (RPV and BOP blowdown);

After 30 minutes after break for long term blowdown calculation, HPCF and RCIC injections will be terminated and LPFL injection will be regulated to maintain water level between L-2 and L-8.


Assumptions

Modeling AssumptionsHomogeneous Moody model is applied to calculate blowdown

flow rate;

The effects of internal choking at Venturi of FW system and Spargers inside RPV are considered;

The pump curves of flow run out are used to model the FWPs;

Flashing of water depressurized below its saturation point and the associated effect of flashing on steam supply are considered;

The effect of stored heat from metal and saturated water stored in feedwater heater shell sides on the feedwater heating are considered;


Results

RPV Short-Term Inboard Break

Time [s] Events

0.000 Feedwater line break.

0.310 L-4 and 10 RIPs Runback (L-4 + 0.0s, not apply).

5.000 Reactor scram by drywell high pressure (Assumption).

5.393 L-3, Trip of 4 RIPs without MG set (L-3 + 0.0s).

12.629 L-8, Turbine trip (L-8 + 0.0s, not apply), and Feedwater pump turbine trip (L-8 + 0.0s, not apply).

19.268 MSIVs closure by main steam line low pressure.

26.742 L-2, Trip of 3 RIPs with MG set (L-2 + 0.0s).

31.000 HPCF startup complete (Drywell high pressure + 26.0s).

32.742 Trip of other RIPs with MG set (L-2 + 6.0s).

34.000 RCIC startup complete (Drywell high pressure + 29.0s).

41.000 LPFL startup complete (Drywell high pressure + 36.0s).

Sequence of Events of FWLB Inboard Break


Results


0 100 200 300 400 500 600 700Time [sec]

-3000

0

3000

6000

9000

12000

15000

Brea

k Fl

ow -

RPV

Sid

e [k

g/se

c]

0 100 200 300 400 500 600 700Time [sec]

-500

0

500

1000

1500

2000

2500

3000

Brea

k Fl

ow E

ntha

lpy

- RPV

Sid

e [k

J/kg

]

Break Flow from RPV Side Break Flow Enthalpy from RPV Side


Results


Reactor Water Levels ECC Injection Flows


Results


Pressure Responses before and after MSIV Flows through both the Intact and Broken FW Lines


Results

BOP Short-Term Inboard Break

Feedwater Pump Run out Speed BOP Blowdown Flow Rate

0 100 200 300 400 500 600 700Time [sec]

-1000

0

1000

2000

3000

4000

FWL

Flow

[kg/

s]

Break Line - BOP SideIntact Line


Results


Local voids near the BOP Break End Comparison of the Local Saturation Temperature against the Coming Water Temperature

(Outboard Check Valve)(To RPV) (Venturi)

Feedwater Line Header

Feedwater Line A

Feedwater Line B

Inboard BreakNode

(Inboard Check Valve)

Outboard Break Node

Primary Containment Wall


Results


Extraction Steam Flow from Low Pressure Turbine Feewater Heater Shell Side Pressures


Results


0 100 200 300 400 500 600 700Time [sec]

-200

0

200

400

600

800

1000

1200

Brea

k Fl

ow E

ntha

lpy

- BO

P Si

de [k

J/kg

]

0 30 60 90 120 150 180Time [sec]

0

200000

400000

600000

800000

1000000

Brea

k Fl

ow E

ntha

lpy

[J/k

g]

RELAP5-3D - APKPSAR

BOP Blowdown Enthalpy Comparison BOP Blowdown Enthalpy against PSAR Curve


Results


0 30 60 90 120 150 180Time [sec]

-1000

0

1000

2000

3000

4000

5000

Brea

k Fl

ow [k

g/se

c]

RELAP5-3D - APKPSAR

Comparison of the Blowdown Flow against PSAR Curve

0 30 60 90 120 150 180Time [sec]

-100000000000

0

100000000000

200000000000

300000000000

400000000000

Brea

k Fl

ow E

nerg

y In

tegr

atio

n [J

]

RELAP5-3D - APKPSAR

Comparison of the Accumulated Blowdown Energy against PSAR


Conclusions

The blowdown licensing analysis of FWLB have been successfully analyzed by the advanced RELAP5-3D/K, which include

Inboard & Outboard breakRPV & BOP blodwodnShort term & long term

All essential processes involved can be adequately simulated by RELAP5-3D/K:

(1) critical flow at the break ends or the internals, (2) flashing of RPV inventory and FW near the break,(3) run out and coast down of the FW pumps;(4) steam extractions to FW heaters and FWP turbines;(5) flashing of saturated water initially stored inside systems;(6) energy release from saturated water and system metal,(7) cold water transportation from condenser to the break; and(8) ECC injections and associated level variations.


Conclusions

Through comparisons against the PSAR curves for the inboard break, it was observed that

The revised accumulated blowdown mass can be bounded in the first 180 seconds,The revised accumulated blowdown energy can only be bounded in the first 120 seconds.


Special Issue of LPFL Injection Bypass

What is the LPFL Injection Bypass?A two-phase mixture water column with cold ECC water above might exist in the DCM during a FWLB event.The effective hydraulic head of this mixture water is not enough to bring the DCM water into the core core.Once DCM water level ascends to the FW rings, all the LPFL injection water will be directly driven to the break without entering the core shroud. RIP

LPFLTAF

DCM



0 100 200 300 400 500 600 700Time [sec]

30

40

50

60

70

80

Supp

ress

ion

Pool

Liq

uid

Tem

pera

ture

[o C]

S/P Temperature - GE SupplyS/P Temperature - PDM



RPV Water Level Responses Balance of RPV Boundary Flows

licensing analysis of rpv and bop blowdown for the event of … · 2017-05-22 · lp turbine#6 tdv...

Documents